Search by property

This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.

List of results

• ML20141H602  + (To PP-07, Discrepancy Repts)
• ML033650203  + (To PRA03-12, Risk Assessment of Turbine Missiles While Transporting Loaded Casks on the Humboldt Bay Transport Route)
• ML033650206  + (To PRA03-14, Risk Assessment of Aircraft Hazard for Dry Cask/Spent Fuel Transportation and Storage at the Humboldt Bay Isfsi)
• ML033650375  + (To PSA-039, PSA Assessment for ESW Pump a Unavailability)
• ML17313A579  + (To PVNGS SG Tube ISI Results for Seventh Refueling Outage Mar & Apr 1998)
• ML13333A933  + (To PWR Safety & Relief Valve Adequacy Rept for San Onofre,Unit 1. Safety Valve Discharge Piping Adequacy Analysis Encl.W/Four Oversize Drawings.Aperture Cards Are Available in PDR)
• ML19318C999  + (To Pages SAR (Application) for Model NP-50ssL Casks)
• ML19318C426  + (To Part 21 Rept Re Failed Thrust Bearing.Insp Complete.Crankshaft Thrust Bearings on Two Diesel Generators Are Free of Reported Potential Defect)
• ML17116A318  + (To Permanently Defueled Emergency Plan (Volume 1, PDEP-1))
• CY-05-119, To Physical Security Plan  + (To Physical Security Plan)
• PLA-6609, To Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Security and Contingency Plan for Independent Spent Fuel Storage Facility, PLA-6609  + (To Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Security and Contingency Plan for Independent Spent Fuel Storage Facility, PLA-6609)
• ML13310A237  + (To Plant Shutdown from Full Power to Hot Standby)
• ML13310A240  + (To Plant Shutdown from Hot Standby to Cold Shutdown)
• ML19242B738  + (To Plant Steam Generator Repair Rept)
• ML17276B699  + (To Plant Verification Rept, Dtd Oct 1982)
• ML20114F830  + (To Preliminary Assessment of Core Melt Probability in Cold Shutdown Following Postulated LOCA at Sequoyah Nuclear Plant, Final Rept)
• ML19345F288  + (To Preliminary Draft, Analysis of Comments Received on NRC Advance Notice of Rulemaking:Revision of Reactor Siting Criteria, (45FR50350,800729))
• ML20053C067  + (To Preservice Insp Automated Exams Scan Plan for Reactor Vessel Welds)
• ML19331B541  + (To Preservice Insp Program Plan)
• ML19309H440  + (To Preservice Insp Program Plan 80A0482)
• ML20052A516  + (To Procedure 0120032, Excessive RCS Activity)
• ML20050A551  + (To Procedure 0291A, Meteorological Monitoring, Offsite Dose Calculation Program for Emergency Preparedness at Operating Nuclear Power Plants)
• ML20052G861  + (To Procedure 58.001.01, Receipt,Insp & Channeling of Unirradiated Fuel)
• ML20053C355  + (To Procedure 58.007.01, Inventory,Status & Control of Snm)
• ML20052G865  + (To Procedure 58.007.01, Inventory,Status & Control of Snm)

• ML20052G869  + (To Procedure 68.003.01, Receiving Radioactive Matls)

• ML20042B816  + (To Procedure 74170-5, Procedure for Repair to Closure Head Flange and CEDM Welds)
• ML20066C431  + (To Procedure 80A2950, Ultrasonic Exam Procedure for Flued Head Welds. Field Change 1 Authorization Encl)
• ML18017B699  + (To Procedure 80A5035, Reactor Pressure Vessel Preservice Insp Program Plan)
• ML040700544  + (To Procedure EI-14, Medical Care/Treatment of Contaminated, Injured Personnel)
• ML032250404  + (To Procedure EP-PS-243, Radiological Liaison)
• ML17273A077  + (To Procedure EVP-001/SL-2, Engineering Verification Program)
• ML20049K019  + (To Procedure FNP-2-M-019, Inservice Testing Program for ASME Class 1,2 & 3 Pumps & Valves)
• ML040400210  + (To Procedure No. EI-15.2, Communications Tests)
• ML020990104  + (To Procedure No. EI-2.2, Emergency Staff Augmentation)
• ML031681374  + (To Procedure No. El-13, Evacuation/Reassembly)
• ML20050D491  + (To Procedure OAP1895.00N, ALARA Program)
• ML20050D495  + (To Procedure OAP1895.01N, ALARA Reviews)
• ML20050D496  + (To Procedure OAP1895.02N, ALARA Committee)
• ML20050D511  + (To Procedure OAP1897.00N, Radiation Protection Manual)
• ML20053A252  + (To Procedure OI-RC-7, RCS Pressure Control)
• ML20053A193  + (To Procedure OP-2-1, Plant Startup from Cold Shutdown to Hot Standby)
• ML20053A206  + (To Procedure OP-6-1, Hot Standby to Cold Condition)
• ML20053A224  + (To Procedure OP-8-1, Reactor Shutdown)
• ML20005A396  + (To Process Control Program)
• ML20042C297  + (To Process Control Program)
• ML20041E659  + (To Process Control Program)
• ML023470300  + (To Process Safety Requirements PSR-1, Requirements for Liquid Transfers of Fissile Material)
• ML20151G868  + (To Product Spec Itt Grinnell Corp Figure 670 Hydraulic Shock Suppressor)
• ML13302A525  + (To Program Plan for Piping Verification Program (Thermal Expansion,Steady State Vibration & Dynamic Effects))
• NUREG/CR-6850, To Propose an Alternative Methodology to Distribute Transient Ignition Frequencies (Bins 3, 5, 6, 7, 11, 24, 25, 31, 36, 37) That Contains a More Structured Approach to Accounting for Influence Factor Variations within a Pau  + (To Propose an Alternative Methodology to Distribute Transient Ignition Frequencies (Bins 3, 5, 6, 7, 11, 24, 25, 31, 36, 37) That Contains a More Structured Approach to Accounting for Influence Factor Variations within a Pau)